SYMPOSIA PAPER Published: 01 January 1994
STP15154S

Dosimetry Aspects of the New Canadian MAPLE-X10 Reactor

Source

Atomic Energy of Canada Limited is building the 10-MWt MAPLE-X10 reactor facility as a dedicated producer of medical and industrial radioisotopes. Dosimetry aspects of the MAPLE-X10 nuclear design include the calculated thermal and fast neutron flux distributions throughout the reactor assembly and the rate of heat generation in reactor materials and components. Examples of the resolution of design issues are also presented, such as the use of fission counters and ion chambers to provide diverse methods of detecting neutron flux levels and the use of the difference between photon and neutron signals to guard against the effects of downgrading of the heavy-water reflector. Computer codes employed in the calculations include MCNP, ONEDANT, WIMS-AECL, and 3DDT.

Author Information

Lidstone, RF
Reactor Technology Branch, AECL Research, Whiteshell Laboratories, Pinawa, MB, Canada
Wilkin, GB
Reactor Technology Branch, AECL Research, Whiteshell Laboratories, Pinawa, MB, Canada
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Details
Developed by Committee: E10
Pages: 588–597
DOI: 10.1520/STP15154S
ISBN-EB: 978-0-8031-5281-6
ISBN-13: 978-0-8031-1899-7